On computing the effective multiplication factor using the ADO method

Abstract In this work, the Analytical Discrete Ordinates method, ADO method, is applied to evaluate the effective multiplication factor in criticality problems of a nuclear reactor. To address this class of problems, the multigroup ADO formulation in multislab geometry is here derived taking into account real and complex spectrum. Two approaches are presented to find the desired dominant k-eigenvalue. In the first one, a criticality (characteristic) equation is derived from the complete original equation defined in multiplying media and a combined scheme, using regula-falsi and secant root-finding methods, is used to extract a root of that equation. Such scheme is shown to be very efficient and provided high-quality benchmark results, from lower quadrature order approximations than other schemes available in the literature, as found by the application of the ADO formulation also in several other transport problems. As a second proposed approach, the ADO solution is used along with the usual power iteration method in a simpler procedure. This simpler procedure avoids complex eigenvalues, but it is shown to be less accurate due to required approximations in the source approximation procedure.

[1]  Ed Anderson,et al.  LAPACK Users' Guide , 1995 .

[2]  C. E. Siewert,et al.  A discrete-ordinates solution for a non-grey model with complete frequency redistribution , 1999 .

[3]  C. Siewert,et al.  An analytical discrete-ordinates solution for dual-mode heat transfer in a cylinder , 2002 .

[4]  Gene H. Golub,et al.  Matrix computations , 1983 .

[5]  Dan G. Cacuci,et al.  Handbook of Nuclear Engineering , 2010 .

[6]  C. E. Lee,et al.  Analytical solutions to the moment transport equations-II: Multiregion, multigroup 1-D slab, cylinder and sphere criticality and source problems , 1985 .

[7]  Hesham Shahbunder,et al.  Study on criticality and reactivity coefficients of VVER-1200 reactor , 2020 .

[8]  R. Rulko Variational derivation of multigroup P2 equations and boundary conditions in planar geometry , 1995 .

[9]  On computing the eigenvalue spectrum and elementary solutions of multigroup diffusion equations for neutron multiplication eigenvalue problems , 2007 .

[10]  C. Siewert A spherical-harmonics method for multi-group or non-gray radiation transport , 1993 .

[11]  J. Duderstadt,et al.  Nuclear reactor analysis , 1976 .

[12]  J. Douglas Faires,et al.  Numerical Analysis , 1981 .

[13]  P. Saracco,et al.  An alternative observable to estimate keff in fast ADS , 2016, 1604.05075.

[14]  R.D.M. Garcia,et al.  On criticality calculations in multislab geometry , 2001 .

[15]  THE PN METHOD FOR CELL CALCULATIONS OF PLATE-TYPE FUEL ASSEMBLIES , 2001 .

[16]  A. Ahlin,et al.  Transmission Probability Method of Integral Neutron Transport Calculation for Two-Dimensional Rectangular Cells , 1975 .

[17]  R. Sánchez Some bounds for the effective multiplication factor , 2004 .

[18]  M. Vilhena,et al.  Determination of the effective multiplication factor in a slab by the LTSN method , 1999 .

[19]  Vincent Heuveline,et al.  The Davidson method as an alternative to power iterations for criticality calculations , 2011 .

[20]  A study on boundary fluxes approximation in explicit nodal formulations for the solution of the two-dimensional neutron transport equation , 2019, Progress in Nuclear Energy.

[21]  The ADO-nodal method for solving two-dimensional discrete ordinates transport problems , 2017 .

[22]  Edward J. Allen,et al.  The inverse power method for calculation of multiplication factors , 2002 .

[23]  C. Siewert,et al.  A Discrete-Ordinates Solution for a Polarization Model with Complete Frequency Redistribution , 1999 .

[24]  A NEW VERSION OF THE DISCRETE-ORDINATES METHOD , 2001 .

[25]  C. E. Siewert The critical problem with high-order anisotropic scattering , 2001 .

[26]  Siraj-ul-Islam Ahmad,et al.  NEUTRONICS ANALYSIS OF TRIGA MARK II RESEARCH REACTOR , 2017 .

[27]  L. Barichello,et al.  An analytical approach for a nodal scheme of two-dimensional neutron transport problems , 2011 .

[28]  R. T. Ackroyd,et al.  A finite element method for neutron transport. Part IV: A comparison of some finite element solutions of two group benchmark problems with conventional solutions , 1980 .

[29]  Y. Azmy,et al.  Tort solutions to the three-dimensional MOX benchmark, 3-D Extension C5G7MOX , 2006 .

[30]  S. Shiroya,et al.  Accelerator driven subcritical system as a future neutron source in Kyoto University Research Reactor Institute (KURRI) —Basic study on neutron multiplication in the accelerator driven subcritical reactor— , 2000 .

[31]  L. Barichello,et al.  An analytical discrete ordinates nodal solution to the two-dimensional adjoint transport problem , 2020 .

[32]  C. E. Siewert,et al.  Unified solutions to classical flow problems based on the BGK model , 2001 .